• Nuclear Engineering and Technology
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• v.25 no.3
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• pp.480-496
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• 1993

원자력발전 핵연료주기에서 고려하여야 할 중요한 요소의 하나는 사용후핵연료에서 비롯되는 고준위 방사성핵종이다. 고준위 방사성핵종의 처분 방법으로서 심지층처분방식은 가장 손쉬운 방법이기는 하나 매우 장시간의 감시가 필요하며, 특히 자연환경으로의 누출가능성이 커서 이의 대안으로서 외국 몇 나라에서는 소위 소멸처리(Transmutation)방법에 대한 연구를 활발히 하고 있다. 현시점에서 소멸처리 방법으로 가장 타당성이 있는 것으로 여겨지는 것은 원자로를 이용하는 것과 가속기 구동 미임계 시스템 (Accelerator-Driven Subcritical System)을 이용하는 방법이다. 본 기고문에서는 이들 방법을 중심으로 다양한 소멸처리 방법의 소개와 기술적인 문제점(특히 핵 특성관점에서)에 대한 고찰 그리고 향후 연구과제 등에 대하여 기술하고자 한다. 비록 소멸처리 시스템의 현실화를 위해서는 해결되어야 할 과제가 많이 남아 있지만, 기술적인 가능성과 방사능의 소멸이란 면을 고려할 때 소멸처리시스템은 궁극적인 방사성핵종 처리기술로서 연구·개발할 충분한 가치가 있는 것으로 판단된다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.131-132
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• 2004

원자력연구소에 보관 중인 오염 토양폐기물을 토양 세척법으로 제염하여 비 방사성폐기물화 한다면 그 부피를 10% 이하로 저감시킬 수 있으며 연구소의 고체 방사성폐기물 저장 용량을 크게 늘릴 수 있다. 1988년 발견 당시 오염 토양 폐기물의 주요 방사성 핵종은 Co-60 이었는데 시간경과에 따라 Cs-134, 137 이 주요 방사성 핵종이 되었다. 오염토양 폐기물의 60 % 이상은 방사능 농도가 극히 낮아 물리적으로 입도를 분리하거나 수 세척에 의해 비 방사성폐기물화 할 수 있음을 파악하였다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.1
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• pp.41-54
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• 2013

Radionuclide sorption data is necessary for the safety assessment of radioactive waste disposal. However the use of sorption database is often limited due to the accessability. A web-based sorption database program named KAERI-SDB has been developed to provide information on the sorption of radionuclides onto geological media as a function of geochemical conditions. The development of KAERI-SDB was achieved by improving the performance of pre-existing sorption database program (SDB-21C) developed in 1998 and considering user's requirements. KAERI-SDB is designed that users can access it by using a web browser. Main functions of KAERI-SDB include (1) log-in/member join, (2) search and store of sorption data, and (3) chart expression of search results. It is expected that KAERI-SDB could be widely utilized in the safety assessment of radioactive waste disposal by enhancing the accessibility to users who wants to use sorption data. Moreover, KAERI-SDB opened to public would also improve the reliability and public acceptance on the radioactive waste disposal programs.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.4
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• pp.419-427
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• 2019

The application of ion crystallization technology was considered as a way to increase the operating efficiency and improve the operating performance of a liquid waste management system (LWMS) in the Advanced Power Reactor 1400 (APR 1400). Although ion crystallization technology has not been practically applied to Nuclear Power Plants (NPPs) until now, a previous experimental study demonstrated that it is possible to selectively remove at least 95% of various nuclide ions present in the liquid radioactive waste of NPPs. We reviewed the possibility of applying ion crystallization technology to the existing LWMS by applying the nuclide removal rate of ion crystallization technology and prepared a way to improve the existing LWMS in the APR 1400. Furthermore, we determined the optimized application location of ion crystallization technology in the existing LWMS by considering decontamination characteristics of the ion crystallization technology and the existing LWMS design features and operating experiences. The application of ion crystallization technology to the liquid waste collection tank, where liquid radioactive materials are collected, will have the least impact on the existing design while providing the greatest improvement. It is expected that the application of ion crystallization technology to the current APR 1400 or new NPPs would increase the operating efficiency of the LWMS and result in an improvement of system performance.

• Journal of Korean Society of Environmental Engineers
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• v.37 no.8
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• pp.465-471
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• 2015

Adsorption experiments for radionuclides such as $^3H$, $^{90}Sr$ and $^{99}Tc$ were conducted using fractured rock collected in unsaturated zone. The released radionuclide through artificial barrier from the near surface repository can be transported by the flow of rainfall or pore water through fractures in unsaturated zone and reach to groundwater flow. Therefore, it is important to investigate transport behavior (retardation) of radionuclides through fractured rock for the safety assessment and long-term performance of repository. Fractured rock samples were collected and characterized by X-ray microtomography (XMT) analysis, which can be used to develop a more robust unsaturated fracture transport model. When fracture-filling materials are exist, distribution coefficient of $^{90}Sr$ is higher than without fracture-filling materials. In this study, batch sorption distribution coefficient ($K_d$) of radionuclide was determined and used to increase our understanding of radionuclide retardtion through fracture-filling materials.

• The Journal of the Petrological Society of Korea
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• v.17 no.3
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• pp.179-190
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• 2008

The distribution characteristics of some major environmental radionuclides ($^{40}K$, $^{228}Ac$, $^{226}Ra$, $^{222}Rn$) and U in rocks, soils and soil gas were studied at Geumjeong-Gu, Busan, Korea. The activities of radionuclides in granitic rocks are decreased in the odor of $^{40}K$>thorium decay series>uranium decay series. This reveals that Th was relatively more enriched in granitic rocks than U. The U content and activity of $^{226}Ra$ and $^{228}Ac$, however, don't reflect the fractionation sequence of granitic rocks in the study area. The activities of all these radionuclides and U content in soils are generally higher than in rocks, and their distribution in rocks, soils and soil gas show very low co-relationship. These facts indicate that the activities of radionuclides in soil and soil gas were greatly affected by leaching and adsorption properties of the radionuclides and their parents during weathering and pedogenetic process rather than their concentrations in parent rocks.

• The Journal of the Korea Contents Association
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• v.9 no.11
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• pp.240-246
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• 2009

Quality control test in this field of study were carried out in 3 categories, radionuclidic purity, chemical purity and radiochemical purity. Also, indication efficiency was tested every 3 hours changed after binding the radiopharmaceutical to see how long the medicine is available for usage after indicating. The result showed that currently used radiopharmaceutical have good radionuclidic purity and chemical purity. However, radiochemical purity indication showed small differences depending on indication method and indication period. Radiopharmaceutical are indicated by treatment providers, so they need to pay more attention to the indication process and quality control to provide more efficient treatment.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 2004.09a
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• pp.406-409
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• 2004

최근 Lee et al.$^{l-2)}$ 은 화강암질 편마암내 균열면의 방해석이 Eu의 변화에 큰 영향을 주며, 아울러 Eu 은 Am의 유사체로서 매우 적합한 원소라고 제안하였다. 이 논문에서는 1)희토류원소와 액티나이드 원소의 이온반경, 배위수 등의 상호비교와 2) 응집력(cohesive energy)의 유사성과 물리적/화학적 특성 그리고 3) 희토류원소 지구화학의 최근 연구결과를 토대로 하여, 고준위 방사성 핵종원소인 Am의 지질매체내 거동을 예측하기 위한 유사체(analog)로서 Eu이 매우 유용한 역할을 해준다는 가설2)을 검증한 결과를 보고하고자 한다. 연구방법으로서, 핵종원소의 지질매체별 흡착특성을 밝혀내기 위해 금번 실험에서는 희토류원소 암상별 분포의 특성을 고려하여 4종류(화강암질 편마암류 2종, meta-basalts, 응회암)의 시료를 선별하였다. 방사화학적 흡탈착 실험의 핵종동위원소로서는 152Eu와 241Am을 선택하였다. 이는 본 연구팀의 연구결과, Eu과 Am의 밀접한 물리적/화학적 상관관계 그리고 지질환경내에서의 거동특성을 고려한 것이다. 실험결과 양 동위원소의 지질매체와의 흡착 반응 특성을 비교해 볼 때, 시간의 경과에 따라 서로간에 매우 유사한 양상의 증감을 보여주면서 변화함을 알 수가 있었다. 이 결과는 희토류원소가 액티나이드 원소의 지질환경내 거동예측을 위한 유사체로서 매우 훌륭한 도구라는 것을 입증해 주는 것이라 할 수 있다.

• Nuclear Engineering and Technology
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• v.26 no.2
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• pp.277-284
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• 1994

Much attention has been given to predict the near-field mass transfer of a single radioactive species from a waste solid into surrounding porous medium. But only limited considerations have been given to predict the coupled mass transfer of species with a radioactive decay chain. In this study we present an analysis assuming that the members of a decay chain dissolve congruently with a solubility-limited matrix. We give general, non-recursive analytic solutions for the transport of a radioactive decay chain in a finite porous medium when nuclides are released congruently with the matrix. As an illustration we consider the decay chain $^{234}$ Ulongrightarrow$^{230}$ Thlongrightarrow$^{226}$ Ra from spent fuel. These solutions may be useful and potentially important in performance assessment of radioactive waste repositories.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.52-57
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• 2004

In order to analyze key parameters of important radionuclides in dose evaluation model of decommissioning site, a sensitivity analysis was performed. This analysis assumed a resident farmer for an exposure scenario and 0.037Bq/g for the concentration of radionuclides. As a result of sensitivity analysis, the key parameters of radionuclides considered were the area of contaminated zone, external gamma shielding factor and indoor time fraction for Cs-137 and Co-60. The key parameters for C-14 were the environmental parameters and hydrological parameters of unsaturated zone. Also, the key parameter for Sr-90 was the density of contaminated zone.